ML20058N371

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Advises That Programmed Enhancements for Generic Ltr 88-17, Loss of DHR, Acceptable
ML20058N371
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/10/1990
From: Bournia A
Office of Nuclear Reactor Regulation
To: Gates W
OMAHA PUBLIC POWER DISTRICT
References
GL-88-17, TAC-69744, NUDOCS 9008140084
Download: ML20058N371 (4)


Text

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- ,' g, UNITED STATES NUCLEAR REGULATORY COMMISSION -i ij- r, " . >j _ WA$HING T ON, D. C. 20655

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. August 10, 1990 -

Docket.No. 50-285 j Mr. W. Gary Gates Division Manager - Nuclear Operations

-Omaha Public Power District 444 South 16th Street liall  ;

Mail Stop BE/EP4 Omaha, Nebraska 68102-2247

Dear Mr. Gates:

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SUBJECT:

PROGRAMMED ENHANCEliENTS FOR GENERIC LETTER 88-17 " LOSS OF DECAY HEAT' REMOVAL" FT. CALHOUN STATION, UNIT 1 (TAC NO. 69744)

The NRC staff has completed its review of all licensees' responses regarding  ;

progranned enhancements as defined in Aeneric Letter (GL) 88-17 " Loss of Decay! t Heat Removal." The NRC staff review was based on a-sampling of about one-third of all responses. Since the sample did not result in significant comments, the remainder of the responses will not be reviewed by NRR. NRC review.of-this phase of GL 88-17 will be accomplished as an inspection under Temporary

  • Instruction (TI) 2515/103 in the NRC Inspection Manual. The inspection will-take place after you have made sufficient progress for NRC to make a full assessment of your programmed enhancements. This letter constitutes the NRR report stated in paragraph 05.01 as.a prerequisite to the inspection under TI 2515/103.

As for your implementation schedule, you indicated that all hardware-related modifications were completed by your 1990 refueling outage. Since this completion. >

date was by the end of the second refueling outage following receipt of GL '

88-17, your schedule is consistent ~with the GL and is acceptable. _ Also, you indicated that in addition you will. include a Shutdown Cooling Low Flow alarm-and a pressure indication at the Low Pressure Safety Injection and Containment Spray Pumps suction. You further specified that these instrumentations add program enhancements but are not considered requirements. Therefore, you .

indicated that the installation would occur during the 1991 Refueling Outage as a plant improvement item. These items will be incorporated as part of the inspection as discussed above.

Additionally, you are requested to inform the NRC in writing,of any signifi-cant changes in the estimated completion schedule identified above. You are also requested to inform the NRC in writing when this action has actually been-j implemented and the modifications are determined to be operational.

This request is covered by Office of Management and Budget Clearance Number-3150-0011, which expires January 31, 1991. The estimated average burden-hours is 4 person-hours per owner response, including searching data sources, gathering and analyzing the data, and preparing the letter. These estimated '

average burden-hours pertain only to the identified response-related matters and do not include the time for actual implementation of the requested action, j Mosf40084 900810 /

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i. August 10, 1990 W. Gary Gates Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C. 20503.

Please contact us should you have any questions regarding this matter.

Sincerely, g sis s id N~

Anthony Bournia, Project Manager Project Directorate IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION CDocket2E11e NRC PDR Local PDR PD4-1-Reading B. Boger MS 13E4 T. Quay L. Berry T. Bournia 0GC MS15B18-Rockville E. Jordan MS MNBB 3701 ACRS(10)MSP-315 PD4-1 Plant File Region IV, P. Harrell DRP

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NAME :LBerry :TBournia :RJo es :TQuay  :

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DATE :08/b/90 :08/A'/90 :08 /90 :08/ 9 /90  :  :

0FFICIAL RECORD COPY Document Name: GL 8817/LTR

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W. Gary Gates ..

l Send comments regarding this burden estimate or any otSer aspect of this collection of information, including suggestions for reducing this burden, to the Information and Rccords Management Branch, Division of Information Support Services, Of fice of Information Resources Management, ll.S. Nuclear Regulatory  !

Commission, Washington, D.C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D.C. 20503.

l Please contact us should you have any questions regarding this matter.

Sincere'y, dvaja~j $ ctns-Anthony Bournia, Project Manager Project Directorate IV-1 Division of Reactor Projects - 111, IV, Y and Special Projects Office of Nuclear Reactor Regulation cc: See next page i

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Mr. W.' Gary Gates

- Omaha Public Power District Fort Calhoun Station, Unit No..1 a

-1 cc:

l Harry H. ' Voigt. . Esg. ,

L LeBoeuf, Lamb, Leiby 8.MacRae '

1333 New Hampshire Avenue, NW Wasnington, D.C. 20036 Mr. ' Jack Jensen, Chairman-

' Washington County Board-of Supervisors Blair, Nebraska 68008' Mr. Raymond PL Mullikin, Resident Inspector ,

l- U.S. Nuclear; Regulatory .Comission Post Office Box 309 -t Fort Calhoun., Nebraska 68023 Mr. Charles ~B. Brinkman, Manager  !

Washington Nuclear Operations Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Regional' Administrator,_ Region IV U.S. Nuclear Regulatory Comission-L Office of Executive Director for Operations-L 611 Ryan Plaza Drive, Suite 1000 l

Arlington, Texas 76011 Harold Borchert Director i Division of Radiological Health-Nebraska-Department of Health t

-301 Cent 4ar,ial Mall, South 1 Post Office Box 95007 Lincoln, Nebraska 68509 Mr. T. L. Patterson, Manager  ;

Fort Calhoun Station.

Post Office Box 399 .

4 Fort Calhoun, Nebraska 68023 1

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